Search results for "BERYLLIUM"

showing 10 items of 65 documents

Efficient and robust photo-ionization loading of beryllium ions

2017

We demonstrate the efficient generation of Be$^+$ ions with a 60 ns and 150 nJ laser pulse near 235 nm for two-step photo-ionization, proven by subsequent counting the number of ions loaded into a linear Paul trap. The bandwidth and power of the laser pulse are chosen in such a way that a first, resonant step fully saturates the entire velocity distribution of beryllium atoms effusing from a thermal oven. The second excitation step is driven by the same light field causing efficient non-resonant ionization. Our ion-loading scheme is more than 15 times more efficient as compared to former pathways using two-photon continuous wave laser excitation.

Materials sciencePhysics and Astronomy (miscellaneous)Atomic Physics (physics.atom-ph)FOS: Physical sciencesGeneral Physics and Astronomychemistry.chemical_elementApplied Physics (physics.app-ph)02 engineering and technology01 natural sciences7. Clean energyPhysics - Atomic PhysicsIonlaw.inventionlawIonization0103 physical sciencesPhysics::Atomic Physics010306 general physicsGeneral EngineeringPhysics - Applied Physics021001 nanoscience & nanotechnologyLaserchemistryContinuous waveIon trapBerylliumAtomic physics0210 nano-technologyExcitationLight fieldApplied Physics B
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Tritium distribution and chemical forms in the irradiated beryllium pebbles before and after thermoannealing

2011

Abstract Beryllium pebbles are foreseen as a neutron multiplier in the tritium breeding blanket of the future fusion devices. Tritium inventory in the beryllium as a result of neutron-induced transmutations is a significant safety and technological issue for the operation of the breeding blanket. In this study, beryllium pebbles from 3 different irradiation experiments: BERYLLIUM, EXOTIC 8/3-13 and PBA, performed at High Flux Reactor HFR have been investigated. The distribution of tritium in the bulk of the pebbles and the abundance ratios of chemical forms of tritium T 0 , T + and T 2 have been analysed before and after the different thermo-annealing experiments. In order to determine the …

Materials scienceScanning electron microscopeMechanical EngineeringRadiochemistrychemistry.chemical_elementThermal treatmentBlanketNuclear physicsNuclear Energy and EngineeringchemistryGeneral Materials ScienceNeutronTritiumIrradiationBerylliumPebbleCivil and Structural EngineeringFusion Engineering and Design
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Activity monitoring of a gaseous tritium source by beta induced X-ray spectrometry

2013

Abstract For monitoring and control of gaseous tritium sources in fuel circulation systems of fusion reactors beta induced X-ray spectrometry (BIXS) seems to be an applicable method. The characteristics of a BIXS monitoring setup built at TLK were examined. A low-noise silicon drift detector (SDD) was used together with two thin beryllium windows evaporated with gold films of 100 nm for efficient X-ray production. The measured X-ray intensity was proportional to the tritium partial pressure and the average detection efficiency was evaluated as 32.6 × 10−8 cps/Bq. A tritium memory effect was revealed. From the results it was concluded that such a monitoring system would be a useful complemen…

Materials scienceSilicon drift detectorSiliconMechanical EngineeringRadiochemistrychemistry.chemical_elementPartial pressureFusion powerMass spectrometryNuclear Energy and EngineeringchemistryBeta (plasma physics)General Materials ScienceTritiumBerylliumCivil and Structural EngineeringFusion Engineering and Design
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Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up

2008

Abstract Within the framework of the R&D activities promoted by European Fusion Development Agreement on the helium-cooled pebble bed test blanket module to be irradiated in ITER, ENEA Brasimone and the Department of Nuclear Engineering of the University of Palermo performed intense research activities on the modelling of the thermo-mechanical behaviour of both beryllium and lithiated ceramics pebble beds, which are envisaged to be used, respectively, as neutron multiplier and tritium breeder. In particular, at the DIN a thermo mechanical constitutive model was developed for both lithiated ceramics and beryllium pebble beds and it was successfully implemented on a commercial finite element …

Materials scienceStructural materialMechanical EngineeringNuclear engineeringConstitutive equationchemistry.chemical_elementBlanketFinite element methodPebble beds Thermo-mechanical constitutive model HCPB-TBMNuclear Energy and EngineeringchemistryMockupGeneral Materials ScienceNeutronBerylliumPebbleSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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On the theoretical–numerical study of the HEXCALIBER mock-up thermo-mechanical behaviour

2010

Abstract Within the framework of the R&D activities promoted by European Fusion Development Agreement on the Helium-Cooled Pebble Bed Test Blanket Module to be irradiated in ITER, ENEA Brasimone and the Department of Nuclear Engineering of the University of Palermo (DIN) performed intense research activities on the modelling of the thermo-mechanical behaviour of both beryllium and lithiated ceramics pebble beds, that are envisaged to be used, respectively, as neutron multiplier and tritium breeder. In particular, the DIN developed a thermo-mechanical constitutive model for these pebble beds to be validated against the HEXCALIBER mock-up test campaign, carried out at the ENEA HE-FUS3 facilit…

Materials scienceTokamakMechanical EngineeringNuclear engineeringchemistry.chemical_elementBlanketFusion powerFinite element methodlaw.inventionPebble beds Thermo-mechanical constitutive model HCPB-TBMNuclear Energy and EngineeringchemistryMockuplawGeneral Materials ScienceNeutronBerylliumPebbleSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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CONCENTRATION MEASUREMENTS OF 7Be AT GROUND LEVEL AIR AT PALERMO, ITALY- COMPARISON WITH SOLAR ACTIVITY OVER A PERIOD OF 21 YEARS

2003

Air activity concentrations of (7)Be in Palermo determined for the period January 1995-December 2002 by gamma-ray spectrometric analysis of particulate samples collected on paper filter by a high-volume sampler (approximately 900 m(3) h(-1)) are reported. The temporal behaviour of (7)Be concentration presents the same characteristics already observed in the measurements carried out over the previous 13-year (1982-1994) investigated period. The mean value of 5.06 mBq m(-3) obtained from the analysis of the 4636 particulate samples collected from 1982 to 2002 can be considered a representative value of (7)Be air concentration at ground level in our geographical zone. The comparison of long-te…

MeteorologyPeriod (periodic table)Health Toxicology and MutagenesisSolar activityAir pollutionAtmospheric sciencesmedicine.disease_causePalermoTroposphere7BemedicinePaper filterEnvironmental ChemistryInverse correlationWaste Management and DisposalRadioisotopesActivity concentrationMean valueGeneral MedicineParticulatesHistory 20th CenturyPollutionTemporal variationGround levelSpectrometry GammaItalyEnvironmental scienceBerylliumCosmic RadiationEnvironmental Monitoring
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Magnetic field effects on tritium release from neutron-irradiated beryllium pebbles

2007

The effects of temperature, magnetic field (MF), and ionizing radiation on the release of tritium from the Be pebbles irradiated in the BERYLLIUM experiment in 1994 in Petten, The Netherlands (irradiation neutron fluence 1.24×10 25 m -2 , irradiation temperature 780 K, and 3 H content 7 appm) were investigated in this study. Simultaneous action of these factors corresponds to the real operating conditions of the blanket of a fusion reactor. The total amount of tritium in a separate pebble, the chemical forms of localized tritium (T 0 , T 2 , and T + ), and the tritium distribution in the pebble volume were determined by a lyomethod (dissolution). Thermoannealing experiments were performed a…

Nuclear and High Energy Physics020209 energyRadiochemistrychemistry.chemical_element02 engineering and technologyFusion powerCondensed Matter PhysicsIonizing radiation020303 mechanical engineering & transports0203 mechanical engineeringNuclear Energy and EngineeringchemistryNeutron flux0202 electrical engineering electronic engineering information engineeringTritiumNeutronIrradiationBerylliumPebble
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Tritium release behavior of beryllium pebbles after neutron irradiation between 523 and 823K

2013

Abstract Post-irradiation tritium release from the Pebble Bed Assembly (PBA) neutron-irradiated beryllium (Be) pebbles (∅ ≈ 1 mm; the total tritium inventory 2–4 GBq/g) was investigated on annealing in He + 0.1% H 2 . Temperature ramps of 2.3 K/min followed by annealing for 1 h at 1310–1320 K resulted in complete detritiation of the PBA Be pebbles. The tritium burst release occurred after a time lag of 1–6.5 h during constant temperature anneals at 1089–1180 K, with the release time measured after reaching the annealing temperature. Tritium burst release was also observed to occur during cool down. Anneals at 1089 K for 8 h and at 1045 K for 23 h caused detritiation of the PBA Be pebbles by…

Nuclear and High Energy PhysicsAnnealing (metallurgy)Radiochemistrychemistry.chemical_elementThermal diffusivityRelease timeTritium releaseNuclear Energy and EngineeringchemistryGeneral Materials ScienceTritiumBerylliumPebbleNeutron irradiationJournal of Nuclear Materials
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Tritium release from beryllium articles for use in fusion devices

2009

Abstract Results obtained on radiation and magnetic field (MF) effects on tritium release at annealing of the beryllium pebbles from the EXOTIC-8-3/13 irradiation are presented in this study and compared with those for other irradiated beryllium materials. Abundance ratios of chemical forms of tritium in the EXOTIC-8-3/13 beryllium pebbles were determined: T 2 – 65%, T 0 – 23%, T + – 12%. A complete detritiation of these pebbles was achieved at 1123 K for 240 min; MF of 2.35 T had no appreciable effect on the tritium release. At 991 K for 240 min, the degree of detritiation was 96.6% without MF; MF of 2.35 T decreased it to 86.7%. At 940 K for 47 min, the degree of detritiation was 60%, 5 M…

Nuclear and High Energy PhysicsFusionTritium releaseNuclear Energy and EngineeringChemistryRadiochemistrychemistry.chemical_elementGeneral Materials ScienceTritiumIrradiationBerylliumNuclear chemistryJournal of Nuclear Materials
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Tritium retention in plasma facing materials of JET ITER-Like-Wall retrieved from the vacuum vessel in 2012 (ILW1), 2014 (ILW2) and 2016 (ILW3)

2021

Abstract ITER-Like-Wall (ILW) project has been carried out at Joint European Torus (JET) to test plasma facing materials relevant to International Thermonuclear Experimental Reactor – ITER [1]. Limiters and an upper dump plate of the vacuum vessel are made of bulk beryllium tiles, whereas for the divertor bulk tungsten and tungsten-coated carbon fibre (CFC) composite tiles are used. During the shutdowns in ILW1 (2012), ILW2 (2014) and ILW3 (2016), selected beryllium tiles were removed from the vacuum vessel. In this study, tiles from three positions were analysed, and analysis results were compared regarding both the tile position in the vacuum vessel and differences in the exploitation con…

Nuclear and High Energy PhysicsITER-Like WallMaterials scienceThermonuclear fusionFuel retentionMaterials Science (miscellaneous)Nuclear engineeringJoint European Toruschemistry.chemical_elementTungstenTritium01 natural sciences010305 fluids & plasmas0103 physical sciences010302 applied physicsDivertorTK9001-9401Nuclear Energy and EngineeringchemistryDeuteriumvisual_artvisual_art.visual_art_mediumJoint European TorusNuclear engineering. Atomic powerTritiumTileBerylliumBerylliumNuclear Materials and Energy
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